NRC-006C Rev. 12 STP 3 & 4 Final Safety Analysis Report 2.1 Limits Imposed on SRP Section II Acceptance Criteria by ABWR Standard Plant The information in this section of the reference ABWR DCD, including all tables, is incorporated by reference with the following site-specific supplements in Table 2.1-1. United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: NUCLEAR INNOVATION NORTH AMERICA LLC (South Texas Project Units 3 and 4) Commission Mandatory Hearing Docket #: 05200012 & 05200013 Exhibit #: NRC-006C-MA-CM01 Identified: 11/19/2015 Admitted: 11/19/2015 Withdrawn: Rejected: Stricken: Other: Limits Imposed on SRP Section II Acceptance Criteria by ABWR Standard Plant 2.1-1 Rev. 12 STP 3 & 4 Final Safety Analysis Report Table 2.1-1 Limits Imposed on SRP Section II Acceptance Criteria by ABWR Design The supplementary information, provided in the column marked "Discussion," consists of a statement as to whether the SRP limits specified for the reference ABWR design are met for the STP 3 & 4 site, and a roadmap to the FSAR sections where further discussion is provided. SRP Section Subject Limits Discussion Geography and Demography 2.1.1 Site Location and None N/A Description 2.1.2 Exclusion Area None N/A Authority and Control 2.1.3 Population None N/A Distribution Nearby Industrial, Transportation and Military Facilities 2.2.1- Identification of Identify potential hazards in the site The potential external hazards 2.2.2 Potential Hazards vicinity that have a probability of in the vicinity of the STP site are in Site Vicinity occurrence >10-7 per year which identified in Subsections 2.2S.1 produce: and 2.2S.2. The only potential (1) missiles more energetic than the external hazard identified with a tornado missile spectra, or frequency near 1 x 10-7 was an (2) pressure effects in excess of the aircraft accident with a design basis tornado. conservatively calculated total impact frequency of 1.09 x 10-7. 2.2.3 Evaluation of Evaluate only those potential An evaluation of the aircraft Potential Accidents hazards identified above. hazards that could impact the STP site is provided in Subsection 2.2S.2.7.2. Although no other external hazards approach a frequency of 1 x 10- 7, other potential external hazards in the vicinity of the STP site are discussed in Subsection 2.2S.3. 2.1-2 Limits Imposed on SRP Section II Acceptance Criteria by ABWR Standard Plant Rev. 12 STP 3 & 4 Final Safety Analysis Report Table 2.1-1 Limits Imposed on SRP Section II Acceptance Criteria by ABWR Design SRP Section Subject Limits Discussion Meteorology 2.3.1 Regional Per Table 2.0-1. The ABWR site parameters Climatology specified in Table 2.0-1 envelop the STP site-specific characteristics related to regional climatology, with the following exceptions, maximum rainfall rate and ambient design temperatures relative to three of the wet-bulb exceedance values. These departures are discussed in Table 2.0-2 (see also STP DEP T1 5.0-1). Further details on regional climatology are provided in Subsection 2.3S.1. 2.3.2 Local Meteorology None N/A 2.3.3 Onsite None N/A Meteorological Measurements Program 2.3.4 Short-Term Show that the site meteorological The design basis accident Diffusion dispersion values as calculated in doses calculated based on the Estimates for accordance with Regulatory Guide STP site meteorological Accidental 1.145, and compared to dose dispersion values are Atmospheric values given in Chapter 15, result in discussed in Subsections 15.2, Releases doses less than stipulated in 10 15.56, and 15.7. The calculated CFR 100 and the applicable doses meet the dose limits portions of SRP Sections 11 and specified in 10 CFR 100. 15. 2.3.5 Long-Term None N/A Diffusion Estimates Hydrology Engineering 2.4.1 Hydraulic Per Table 2.0-1. The ABWR site parameters Description specified in Table 2.0-1 envelop the STP site-specific characteristics related to hydrology. Further details are provided in Subsection 2.4S.1. Limits Imposed on SRP Section II Acceptance Criteria by ABWR Standard Plant 2.1-3 Rev. 12 STP 3 & 4 Final Safety Analysis Report Table 2.1-1 Limits Imposed on SRP Section II Acceptance Criteria by ABWR Design (Continued) SRP Section Subject Limits Discussion 2.4.2 Floods Per Table 2.0-1. The maximum flood level for the STP site is discussed in Subsections 2.4S.2 and 2.4S.4 (see also Table 2.0-2 and STP DEP T1 5.0-1). Site-specific flood protection measures are described in Subsection 3.4.1.1.1. 2.4.3 Probable None N/A Maximum Flood on Streams and Rivers 2.4.4 Potential Dam Demonstrate that failure of existing Failure of the Main Cooling Failures and potential upstream or Reservoir (MCR) would result in Seismically downstream water control the worst case flood level, and Induced structures will not exceed flooding exceeds the SRP limit for the 30.5 cm below grade. reference ABWR design as discussed in Subsection 2.4S.4 see also Table 2.0-2 and STP DEP T1 5.0-1). Site-specific flood protection measures are described in Subsection 3.4.1.1.1. 2.4.5 Probable Probable maximum surge and The probable maximum surge Maximum Surge seiche flooding level 30.5 cm below flooding level is within the SRP and Seiche grade. limit for the reference ABWR Flooding design. Flooding due to seiche effects is considered insignificant at the STP site. See Subsection 2.4S.5 for further details. 2.4.6 Probable Probable maximum tsunami The probable maximum tsunami Maximum Tsunami flooding level 30.5 cm below grade. flooding level for the STP site is within the SRP limit for the reference ABWR design as discussed in Subsection 2.4S.6. 2.4.7 Ice Effects None N/A 2.4.8 Cooling Water None N/A Channels and Reservoirs 2.4.9 Channel Diversion None N/A 2.1-4 Limits Imposed on SRP Section II Acceptance Criteria by ABWR Standard Plant Rev. 12 STP 3 & 4 Final Safety Analysis Report Table 2.1-1 Limits Imposed on SRP Section II Acceptance Criteria by ABWR Design (Continued) SRP Section Subject Limits Discussion 2.4.10 Flooding None N/A Protection Requirements 2.4.11 Cooling Water None N/A Supply 2.4.12 Groundwater Per Table 2.0-1. The groundwater depth in the power block areas for STP 3 & 4 is below the maximum groundwater level of 61 cm (2 ft) below grade as specified in Table 2.0-1. Further information is provided in FSAR Subsection 2.4S.12. 2.4.13 Accidental None N/A Releases of Liquid Effluent in Ground and Surface Waters 2.4.14 Technical None N/A Specifications and Emergency Operation Requirement Limits Imposed on SRP Section II Acceptance Criteria by ABWR Standard Plant 2.1-5 Rev. 12 STP 3 & 4 Final Safety Analysis Report Table 2.1-1 Limits Imposed on SRP Section II Acceptance Criteria by ABWR Design (Continued) SRP Section Subject Limits Discussion Geology, Seismology and Geotechnical Engineering 2.5.1 Basic Geology and None N/A Seismic Information 2.5.2 Vibratory Ground Per Table 2.0-1. The ABWR DCD design Motion parameters specified in Table 2.0-1 related to seismology are enveloped for the STP site. Further details are provided in Subsection 2.5S.2. 2.5.3 Surface Faulting No faulting at or near the ground There is no potential for surface surface is accepted. faulting through the STP 3 & 4 site footprint as discussed in Subsection 2.5S.3. 2.5.4 Stability of Per Table 2.0-1. The ABWR site parameters Subsurface specified in Table 2.0-1 envelop Materials and the STP site-specific Foundations characteristics related to stability of subsurface materials and foundations. Further details are provided in Subsection 2.5S.4. 2.5.5 Surface of Slopes None N/A 2.1-6 Limits Imposed on SRP Section II Acceptance Criteria by ABWR Standard Plant Rev. 12 STP 3 & 4 Final Safety Analysis Report 1.1 Introduction The information in this section of the reference ABWR DCD, including all subsections and figures, as modified by the STP Nuclear Operating Company Application to Amend the Design Certification rule for the U.S. Advanced Boiling Water Reactor (ABWR), "ABWR STP Aircraft Impact Assessment (AIA) Amendment Revision 3," dated September 23, 2010 is incorporated by reference with departures and supplements. STD DEP 1.1-1 STP DEP 1.1-2 STP DEP 10.1-3 (Figure 1.1-2) STD DEP Vendor 1.1.1 Format and Content The information in this subsection of the reference ABWR DCD is incorporated by reference with the following site-specific supplement. The STP Combined License Application (COLA), Part 2, Final Safety Analysis Report (FSAR) incorporates the ABWR DCD, as applicable, by reference, without repeating the information from the DCD. The reference ABWR DCD refers to U.S. ABWR Design Control Document, GE Nuclear Energy, Revision 4 dated March 1997, as approved in 10 CFR Part 52, Appendix A, and as modified by the STP Nuclear Operating Company Application to Amend the Design Certification Rule for the U.S. Advanced Boiling Water Reactor (ABWR), "ABWR STP Aircraft Impact Assessment (AIA) Amendment Revision 3," dated September 23, 2010. The FSAR, as required by the ABWR design certification rule (10 CFR 52, Appendix A, Section IV.A.2.a), maintains the ABWR DCD organization and numbering system.